PL242466A1 - Method of concentration of spent solutions from nuclear power plants - Google Patents

Method of concentration of spent solutions from nuclear power plants

Info

Publication number
PL242466A1
PL242466A1 PL24246683A PL24246683A PL242466A1 PL 242466 A1 PL242466 A1 PL 242466A1 PL 24246683 A PL24246683 A PL 24246683A PL 24246683 A PL24246683 A PL 24246683A PL 242466 A1 PL242466 A1 PL 242466A1
Authority
PL
Poland
Prior art keywords
concentration
nuclear power
power plants
spent solutions
spent
Prior art date
Application number
PL24246683A
Other versions
PL141722B1 (en
Original Assignee
Magyar Asvanyolaj Es Foeldgaz
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Magyar Asvanyolaj Es Foeldgaz filed Critical Magyar Asvanyolaj Es Foeldgaz
Publication of PL242466A1 publication Critical patent/PL242466A1/en
Publication of PL141722B1 publication Critical patent/PL141722B1/en

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/04—Treating liquids
    • G21F9/06—Processing

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Removal Of Specific Substances (AREA)
  • Heat Treatment Of Water, Waste Water Or Sewage (AREA)
  • Separation Using Semi-Permeable Membranes (AREA)
  • Detergent Compositions (AREA)
PL24246683A 1982-06-10 1983-06-10 Method of concentration of spent solutions from nuclear power plants PL141722B1 (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
HU187682A HU185105B (en) 1982-06-10 1982-06-10 Method for producing waste solution concentrates of atomic power station having high salt concantration

Publications (2)

Publication Number Publication Date
PL242466A1 true PL242466A1 (en) 1984-03-12
PL141722B1 PL141722B1 (en) 1987-08-31

Family

ID=10956622

Family Applications (1)

Application Number Title Priority Date Filing Date
PL24246683A PL141722B1 (en) 1982-06-10 1983-06-10 Method of concentration of spent solutions from nuclear power plants

Country Status (7)

Country Link
CS (1) CS422783A2 (en)
DD (1) DD252743A3 (en)
DE (1) DE3321069A1 (en)
FR (1) FR2530856B1 (en)
GB (1) GB2123203B (en)
HU (1) HU185105B (en)
PL (1) PL141722B1 (en)

Families Citing this family (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
HU193209B (en) * 1984-05-21 1987-08-28 Magyar Asvanyolaj Es Foeldgaz Method for increasing the concentratability of nuclear power station radioactive waste solutions
DE4232246A1 (en) * 1992-09-25 1994-03-31 Siemens Ag Process for the destruction of an organic substance
DE102012204415A1 (en) * 2012-03-20 2013-09-26 Areva Gmbh Process for the removal of radioactive contaminants from waste water
RU2652978C1 (en) * 2017-04-12 2018-05-04 Федеральное государственное бюджетное учреждение науки Федеральный исследовательский центр "Кольский научный центр Российской академии наук" (ФИЦ КНЦ РАН) Method for npp liquid waste processing with boron control

Family Cites Families (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
SE398595B (en) * 1973-08-06 1978-01-09 Duni Bila Ab CARDBOARD PLATE
BE838533A (en) * 1976-02-13 1976-05-28 PROCESS FOR DRYING SOLUTIONS CONTAINING BORIC ACID
BE859028A (en) * 1977-09-26 1978-03-28 Belgonucleaire Sa WATER DECONTAMINATION PROCESS
DE3003087A1 (en) * 1980-01-29 1981-07-30 Alkem Gmbh, 6450 Hanau METHOD FOR RECOVERY OF URANIUM AND / OR PLUTONIUM FROM SOLUTIONS WITH HIGH SALT FREIGHT
DE3029147A1 (en) * 1980-07-31 1982-02-25 Kraftwerk Union AG, 4330 Mülheim Treatment of radioactive residue of waste liquor contg. borate - by adjusting sodium boron molar ratio during concn. by evapn.

Also Published As

Publication number Publication date
HU185105B (en) 1984-12-28
CS422783A2 (en) 1989-12-13
DE3321069A1 (en) 1983-12-15
GB2123203A (en) 1984-01-25
FR2530856A1 (en) 1984-01-27
DD252743A3 (en) 1987-12-30
GB2123203B (en) 1986-09-24
FR2530856B1 (en) 1989-11-03
PL141722B1 (en) 1987-08-31

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